235U enrichment or UF6 mass determination on UF6 cylinders with non-destructive analysis methods

MCNP-A General Monte Carlo N-Particle Transport Code

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Isotope Analysis, Trace Element Geochemistry, Isotope Geochemistry +4

Signatures of fissile materials: high-energy γ rays following fission

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Engineering, Nuclear Physics, Physics +6

Measurements of UF₆ Cylinders with Portable Instruments

R.B. Walton, T.D. Reilly, J.L. Parker et al. · Nuclear Technology · 1974 · 27 citations

Engineering, Nuclear Physics, Measurement +17

Identification of Actinides Inside Nuclear Waste Packages by Measurement of Fission Delayed Gammas

F. Carrel, Mehdi Gmar, Frédéric Lainé et al. · 2006 IEEE Nuclear Science Symposium Conference Record · 2006 · 16 citations

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